Helium-cooled, flibe breeder, beryllium multiplier blanket
The concept described for the blanket surrounding a fusion reaction chamber is based on the use of molten fluoride salts to convert fusion energy into electricity and to breed the tritium fuel for the fusion power plant. Helium cools the first-wall and the blanket internals, which consist of a bed of beryllium balls in which neutrons are multiplied. The neutrons are used to breed tritium and also to release extra energy in exothermic nuclear reactions. Tritium is bred in the molten Flibe salt (LiF + BeF/sub 2/) that flows slowly (about 0.1 m/s) in steel tubes and is removed from the salt and the helium by processing both streams. Because the solubility of tritium in Flibe salt is so low, there is a strong driving force for tritium permeation. A 10-..mu..mthick tungsten permeation barrier, deposited by chemical vapor deposition on the salt-carrying tubes, is proposed for preventing excessive tritium permeation into the helium stream. A 1-mm-thick aluminum jacket on the steel steam generator tubes is proposed to prevent excessive tritium permeation into the steam system. Flibe salt has safety advantages with respect to large accidents in that it will not react with air or water, in contrast to liquid lithium. For the first time, a method is proposed for recycling solid material in fusion blankets. To accomplish this, beryllium pebbles were chosen because the pebbles can be loaded into the blanket after manufacturing and, to accommodate radiation-induced swelling, can be moved periodically by flowing. Once the balls have reached their radiation damage lifetime, they can be removed from the blanket for refabrication and recycle.
- Research Organization:
- Lawrence Livermore National Laboratory, University of California Livermore, CA
- OSTI ID:
- 5791017
- Journal Information:
- Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 8:1; ISSN FUSTE
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ALKALINE EARTH METALS
BERYLLIUM
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
BREEDING PELLETS
DESIGN
ELEMENTS
FEASIBILITY STUDIES
FLIBE
FLUIDS
GASES
HELIUM
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MATERIALS
METALS
MOLTEN SALTS
NONMETALS
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
RARE GASES
REACTOR COMPONENTS
SALTS
SHIELDING
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
TRANSITION ELEMENTS
TRITIUM
TUNGSTEN
YEARS LIVING RADIOISOTOPES